Published October 2015 | Version v1
Journal article

Thermal-hydraulic analysis of water cooled breeding blanket of K-DEMO using MARS-KS code

  • 1. Seoul National University, Seoul (Korea, Republic of)
  • 2. National Fusion Research Institute, Daejeon (Korea, Republic of)

Description

Highlights: • The thermal design of breeding blanket for the K-DEMO is evaluated using MARS-KS. • To confirm the prediction capability of MARS, the results were compared with the CFD. • The results of MARS-KS calculation and CFD prediction are in good agreement. • A transient simulation was carried out so as to show the applicability of MARS-KS. • A methodology to simulate the entire blanket system is proposed. - Abstract: The thermal design of a breeding blanket for the Korean Fusion DEMOnstration reactor (K-DEMO) is evaluated using the Multidimensional Analysis of Reactor Safety (MARS-KS) code in this study. The MARS-KS code has advantages in simulating transient two-phase flow over computational fluid dynamics (CFD) codes. In order to confirm the prediction capability of the code for the present blanket system, the calculation results were compared with the CFD prediction. The results of MARS-KS calculation and CFD prediction are in good agreement. Afterwards, a transient simulation for a conceptual problem was carried out so as to show the applicability of MARS-KS for a transient or accident condition. Finally, a methodology to simulate the multiple blanket modules is proposed.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2015.05.029

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2015.05.029;
PII
S0920-3796(15)00327-0;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
98-99
Journal Page Range
p. 1741-1746
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
28. symposium on fusion technology
Acronym
SOFT-28
Dates
29 Sep - 3 Oct 2014
Place
San Sebastian (Spain)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
48006698
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ACCIDENTS; BREEDING BLANKETS; COMPUTER CODES; COMPUTERIZED SIMULATION; DESIGN; REACTOR SAFETY; THERMAL HYDRAULICS; TOKAMAK DEVICES; TWO-PHASE FLOW; WATER
Descriptors DEC
CLOSED PLASMA DEVICES; FLUID FLOW; FLUID MECHANICS; HYDRAULICS; HYDROGEN COMPOUNDS; MECHANICS; OXYGEN COMPOUNDS; REACTOR COMPONENTS; SAFETY; SIMULATION; THERMONUCLEAR DEVICES

Optional Information

Copyright
Copyright (c) 2015 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.